US5200139A - Method and apparatus for protecting a nuclear reactor - Google Patents
Method and apparatus for protecting a nuclear reactor Download PDFInfo
- Publication number
- US5200139A US5200139A US07/731,331 US73133191A US5200139A US 5200139 A US5200139 A US 5200139A US 73133191 A US73133191 A US 73133191A US 5200139 A US5200139 A US 5200139A
- Authority
- US
- United States
- Prior art keywords
- power
- temperature
- nuclear
- core
- signal
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
Links
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
- G21D3/10—Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the present invention relates to protecting nuclear reactors, i.e. to controlling such reactors in such a manner as to enable them at all times to deliver the power that is required for satisfying varying needs, while avoiding as much as possible both unnecessary burning of fuel and any risk of an accident.
- Very strict safety criteria are defined for limiting such risks, in particular with respect to the boilers constituted by such reactors.
- an authorized operating range for the core is defined by a network of straight line limits plotted in a plane (see FIG. 1) in which the coordinates are nuclear power and axial power difference.
- the axial power difference parameter referred to below by the letters DI, is defined as being the difference between the power PH measured at the top of the core and the power PB measured at the bottom of the core.
- the invention is based on creating an inhibit signal for inhibiting instructions to extract the temperature regulation group whenever the reactor operating point leaves the operating domain dangerously. With conventional reactors, leaving the operating domain dangerously is equivalent to leaving it to the right in FIG. 1.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
DI=PH-PB
DT=B.sub.1 -B.sub.2 ·DI
DT/(1+T.sub.3 p)≧DI·(B.sub.1 -B.sub.2)·(1+T.sub.1 p)/(1+T.sub.2 p)
Claims (7)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR9009095 | 1990-07-17 | ||
FR9009095A FR2665014B1 (en) | 1990-07-17 | 1990-07-17 | METHOD AND DEVICE FOR PROTECTING A NUCLEAR REACTOR. |
Publications (1)
Publication Number | Publication Date |
---|---|
US5200139A true US5200139A (en) | 1993-04-06 |
Family
ID=9398803
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US07/731,331 Expired - Lifetime US5200139A (en) | 1990-07-17 | 1991-07-17 | Method and apparatus for protecting a nuclear reactor |
Country Status (8)
Country | Link |
---|---|
US (1) | US5200139A (en) |
EP (1) | EP0467786B1 (en) |
JP (1) | JPH0527075A (en) |
KR (1) | KR100237115B1 (en) |
CN (1) | CN1062230A (en) |
FR (1) | FR2665014B1 (en) |
TW (1) | TW202514B (en) |
ZA (1) | ZA915586B (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2002043077A1 (en) * | 2000-11-24 | 2002-05-30 | Sinelnikova-Muryleva, Elena Irbekovna | Method for protecting nuclear-power reactors |
US6697447B1 (en) | 1999-12-30 | 2004-02-24 | General Electric Company | Maximum extended load line limit analysis for a boiling water nuclear reactor |
US20100111242A1 (en) * | 2007-04-10 | 2010-05-06 | Sture Helmersson | Method for operating a reactor of a nuclear plant |
US20140314194A1 (en) * | 2011-12-29 | 2014-10-23 | Areva Np | Control method for a pressurized water nuclear reactor |
Families Citing this family (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
KR20010044746A (en) * | 2001-03-21 | 2001-06-05 | 진형근 | Moisturizing Rooibos for Skin Care |
US9799416B2 (en) | 2009-11-06 | 2017-10-24 | Terrapower, Llc | Methods and systems for migrating fuel assemblies in a nuclear fission reactor |
US9922733B2 (en) | 2009-11-06 | 2018-03-20 | Terrapower, Llc | Methods and systems for migrating fuel assemblies in a nuclear fission reactor |
US9786392B2 (en) | 2009-11-06 | 2017-10-10 | Terrapower, Llc | Methods and systems for migrating fuel assemblies in a nuclear fission reactor |
EP2497088A4 (en) * | 2009-11-06 | 2017-03-15 | TerraPower LLC | Methods and systems for migrating fuel assemblies in a nuclear fission reactor |
US10008294B2 (en) | 2009-11-06 | 2018-06-26 | Terrapower, Llc | Methods and systems for migrating fuel assemblies in a nuclear fission reactor |
CN104485140B (en) * | 2014-11-13 | 2017-05-10 | 大亚湾核电运营管理有限责任公司 | Nuclear power station reactor protection system testing method and apparatus thereof |
FR3084958B1 (en) | 2018-08-09 | 2020-10-23 | Framatome Sa | OPERATION LIMITATION METHOD OF A NUCLEAR REACTOR |
Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3997767A (en) * | 1973-07-31 | 1976-12-14 | Combustion Engineering, Inc. | Reactor trip on turbine trip inhibit control system for nuclear power generating system |
GB2040522A (en) * | 1979-01-22 | 1980-08-28 | Babcock & Wilcox Co | Nuclear reactor safety systems |
US4222822A (en) * | 1977-01-19 | 1980-09-16 | Westinghouse Electric Corp. | Method for operating a nuclear reactor to accommodate load follow while maintaining a substantially constant axial power distribution |
US4337118A (en) * | 1978-10-16 | 1982-06-29 | Hitachi, Ltd. | Nuclear reactor power monitoring system |
US4399095A (en) * | 1977-12-16 | 1983-08-16 | Westinghouse Electric Corp. | Protection and control system for a nuclear reactor |
EP0212525A2 (en) * | 1985-08-20 | 1987-03-04 | General Electric Company | Transient monitor for nuclear reactor |
US4699749A (en) * | 1985-05-07 | 1987-10-13 | Westinghouse Electric Corp. | Controlling a nuclear reactor with dropped control rods |
-
1990
- 1990-07-17 FR FR9009095A patent/FR2665014B1/en not_active Expired - Lifetime
-
1991
- 1991-07-16 KR KR1019910012137A patent/KR100237115B1/en not_active IP Right Cessation
- 1991-07-16 JP JP3201410A patent/JPH0527075A/en active Pending
- 1991-07-17 US US07/731,331 patent/US5200139A/en not_active Expired - Lifetime
- 1991-07-17 ZA ZA915586A patent/ZA915586B/en unknown
- 1991-07-17 EP EP91402000A patent/EP0467786B1/en not_active Expired - Lifetime
- 1991-07-17 CN CN91104797A patent/CN1062230A/en active Pending
- 1991-09-20 TW TW080107515A patent/TW202514B/zh active
Patent Citations (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3997767A (en) * | 1973-07-31 | 1976-12-14 | Combustion Engineering, Inc. | Reactor trip on turbine trip inhibit control system for nuclear power generating system |
US4222822A (en) * | 1977-01-19 | 1980-09-16 | Westinghouse Electric Corp. | Method for operating a nuclear reactor to accommodate load follow while maintaining a substantially constant axial power distribution |
US4399095A (en) * | 1977-12-16 | 1983-08-16 | Westinghouse Electric Corp. | Protection and control system for a nuclear reactor |
US4337118A (en) * | 1978-10-16 | 1982-06-29 | Hitachi, Ltd. | Nuclear reactor power monitoring system |
GB2040522A (en) * | 1979-01-22 | 1980-08-28 | Babcock & Wilcox Co | Nuclear reactor safety systems |
US4308099A (en) * | 1979-01-22 | 1981-12-29 | The Babcock & Wilcox Company | Nuclear reactor safety system |
US4699749A (en) * | 1985-05-07 | 1987-10-13 | Westinghouse Electric Corp. | Controlling a nuclear reactor with dropped control rods |
EP0212525A2 (en) * | 1985-08-20 | 1987-03-04 | General Electric Company | Transient monitor for nuclear reactor |
US4678622A (en) * | 1985-08-20 | 1987-07-07 | General Electric Company | Transient monitor for nuclear reactor |
Cited By (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6697447B1 (en) | 1999-12-30 | 2004-02-24 | General Electric Company | Maximum extended load line limit analysis for a boiling water nuclear reactor |
US6721383B2 (en) | 1999-12-30 | 2004-04-13 | General Electric Company | Maximum extended load line limit analysis for a boiling water nuclear reactor |
US20050117685A1 (en) * | 1999-12-30 | 2005-06-02 | Casillas Jose L. | Maximum extended load line limit analysis for a boiling water nuclear reactor |
US6987826B2 (en) | 1999-12-30 | 2006-01-17 | General Electric Company | Maximum extended load line limit analysis for a boiling water nuclear reactor |
WO2002043077A1 (en) * | 2000-11-24 | 2002-05-30 | Sinelnikova-Muryleva, Elena Irbekovna | Method for protecting nuclear-power reactors |
US20100111242A1 (en) * | 2007-04-10 | 2010-05-06 | Sture Helmersson | Method for operating a reactor of a nuclear plant |
US8477899B2 (en) * | 2007-04-10 | 2013-07-02 | Westinghouse Electric Sweden Ab | Method for operating a reactor of a nuclear plant |
US20140314194A1 (en) * | 2011-12-29 | 2014-10-23 | Areva Np | Control method for a pressurized water nuclear reactor |
US9947422B2 (en) * | 2011-12-29 | 2018-04-17 | Areva Np | Control method for a pressurized water nuclear reactor |
Also Published As
Publication number | Publication date |
---|---|
EP0467786B1 (en) | 1995-09-20 |
FR2665014B1 (en) | 1992-09-18 |
FR2665014A1 (en) | 1992-01-24 |
KR920003330A (en) | 1992-02-29 |
KR100237115B1 (en) | 2000-01-15 |
JPH0527075A (en) | 1993-02-05 |
ZA915586B (en) | 1992-04-29 |
TW202514B (en) | 1993-03-21 |
CN1062230A (en) | 1992-06-24 |
EP0467786A1 (en) | 1992-01-22 |
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Legal Events
Date | Code | Title | Description |
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AS | Assignment |
Owner name: FRAMATOME Free format text: ASSIGNMENT OF ASSIGNORS INTEREST.;ASSIGNORS:MOURLEVAT, JEAN-LUCIEN;MONTANARI, GERARD;KOCKEROLS, PIERRE;REEL/FRAME:005845/0966 Effective date: 19910727 |
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STCF | Information on status: patent grant |
Free format text: PATENTED CASE |
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Free format text: PAYER NUMBER DE-ASSIGNED (ORIGINAL EVENT CODE: RMPN); ENTITY STATUS OF PATENT OWNER: LARGE ENTITY Free format text: PAYOR NUMBER ASSIGNED (ORIGINAL EVENT CODE: ASPN); ENTITY STATUS OF PATENT OWNER: LARGE ENTITY |
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